恰希玛（Chashma）核电厂土建施工质量保证

文章概述恰希码核电厂土建施工中质量保证活动的５个主要方面：核电厂建造质量保证大纲；管理性程序和工作程序；材料及设备的接收，贮存和装卸；混凝土链和人员的配备与培训。在这５个有效地开展和实施质量保证活动就抓住了核电厂土建施工质量保证活动的主线，就可以保证核电厂土建施工的质量。     

Development of full-scale simulators for nuclear power plants

The structure of full-scale simulators of nuclear power plants and their development are described. The special features of analytical simulators, which are economical tools for training nuclear power plant personnel because they require only a small investment of capital, are described. An industrial technology for developing simulators for nuclear power plants has been adopted and is maintained at a modern level at the All-Russia Scientific-Research Institute of Nuclear Power Plants. A change in the technical policy of the concern Rosénergoatom made it possible to solve, by and large, the problem of equipping nuclear power plants in Russia with simulators. 3 figures, 1 table, 4 references. All-Russia Scientific-Research Institute of Nuclear Power Plants. Translated from Atomnaya énergiya, Vol. 88, No. 6. pp. 407–414, June, 2000.     

核电厂土建施工三大原材料质量控制

核电厂的建造运行是一项系统工程。为了保证核电厂的质量安全,从设计立项到运行使用,每一个环节的工作都对质量安全产生不同程度影响。与之相关的每一步工作都必须做到质量受控。从核电厂建造过程中土建施工环节中的原材料质量控制入手,着重分析了土建施工中钢材、混凝土材料、模板材料三大主材如何实施质量控制和管理。     

核设备制造质量保证大纲的建立与运行实践

质量保证作为核设备制造管理的核心和主要内容,已成为制约核电设备制造国产化的关键因素之一。本文以东方锅炉(集团)股份有限公司(简称东锅)在广东岭澳核电站2×1000MW(电功率)压水堆核岛主设备分包制造中的核质保实践为例,阐述了核设备制造质量保证大纲的建立原则和主要运行方式,以供从事我国核设备制造行业质量保证工作的有关人员参考。     

核设备制造中的项目管理

核电站项目管理首先应完善管理机构。核设备质保大纲和项目管理的组织机构由核电容器部、制造部、质量保证部等5个部门组成。总经理对核承压设备制造质量负全面责任。分管核电工作的副总经理统一负责公司核承压设备制造有关的质量、技术和进度,组织管理部门进行审查。质量管理部部长由总经理授予足够的权力,包括不受经费和进度的约束,以建立和不断完善质量保证大纲,并验证有关部门和人员的执行情况。制造进度计划的编制应该保证实施的可行性、工作的连续性和执行计划的灵活性。对计划应该进行全过程的跟踪,检查计划的实施情况并及时反馈。     

Modular design and construction techniques for nuclear power plants

Modularization has been proposed as a nuclear power plant design-fabrication approach for increasing the quality and reducing the costs of future plants. The work reported describes a methodology for making the modular design and construction process more systematic and efficient. This methodology is applied to both the design and fabrication processes for power plant modules. The design process is enhanced by the utilization of a matrix reordering technique that reveals natural groupings in complex data sets. This technique allows a layout which groups plant systems functionally so that modules increase self-sufficiency and minimize inter-module interaction costs.In an illustration of modular design the ship fabrication methods of product work breakdown structure are applied to a modular nuclear power plant to be built at an on-site factory facility. A comparison of a new modular power plant and a conventional power plant design is performed. Cost penalty indices are defined in order to guide maximization of the economic benefits of a modular design. Economic analyses, for both modular and conventional construction methods, are performed over a range of construction schedules and monetary interest rates to illustrate the potential savings of modular construction. The results of the analyses reported here indicate a typical potential savings of 15% in the capital cost of the modular nuclear power plant versus a conventional one. The most interesting result of this work is that the potential savings derive equally from the design and construction processes.     

核电站核岛物项质量控制信息化实现

根据核电站核岛物项质量管理模式,阐述了核电站核岛物项质量控制信息化实现的设计思路、实现方法和一些关键技术,说明了核岛物项质量控制方式可以提高核岛质量、保证核电站的安全、降低核电站建造和运营成本。     

大亚湾核电站18个月换料设计质量保证大纲的建立与实施

质量保证体系标准ISO9001-94呼国家核安全法规HAF003（91）对质量体系的要求有所差异，这是核行业质量认证组织面临的主要问题。如何才能同时满足两套标准建立体系，中国核动力研究设计院（NPIC）在大亚湾核电厂18个月换料设计论证项目上作了尝试，并建立、实施和不断完善了质量保证体系，制订并实施了专用的质量保证大纲，采取了一系列的控制、验证措施，向法马通公司（FAMATOME）和大亚湾核电厂提供满意的核设计服务产品。     

核电站从设计安全到现实安全的基本思考

文章针对核电站安全提出"设计安全"和"现实安全"的概念,通过分析研究国外核事故与国内核安全质量事件,阐述设计阶段确保核电站安全的设计安全重要性,重点描述了设计安全保障体系内容。并从设计、采购、制造、建造、安装、调试、运行、维护、老化到退役等全生命周期角度分析影响核电站现实安全的关键因素,探讨了全生命周期中的质量保证体系、核安全文化建设、风险指引对策、人因工程管理、信息反馈机制、核安全监管体系等对核电站现实安全的重要意义。     

核电设备质量保证经验

简要介绍了东方锅炉（集团）股份有限公司核电设备质量保证体系在建立和运行中的几点主要经验和体会，并讨论了下步工作中还应加强的几个方面。     

Quality assurance for objects utilizing nuclear power

The basic aspects of quality assurance for purposes of safety of objects utilizing atomic energy are examined. The formulation of quality assurance requirements of a regulatory agency is analyzed, the experience with enterprises in nuclear power and the atomic industry is examined, and current trends in quality assurance, which are reflected in IAEA manuals and ISO series 9000 standards, are analyzed. The relationship between the quality system and the quality assurance program for objects utilizing atomic energy is discussed. 1 figure, 1 table, 7 references. National Science Center YARB of the Federal Nuclear and Radiation Safety Agency of Russia. Translated from Atomnaya énergiya, Vol. 87, No. 3, pp. 230–235, September, 1999.     

Electrical simulation of nuclear reactors

The application of electrical simulation methods to nuclear reactor calculations considerably shortens the time required for the computational work. In this review the advantages and disadvantages of simulators are discussed and an example is given of the simulation of the reactor isotopic composition with the help of the simulator MN-7. The effectiveness of the electrical simulation method for the investigation of non-stationary reactor processes is shown by an example of design calculations carried out for an automatic power regulator for a reactor. It is shown that it is possible to simulate nonstationary processes occurring in a power reactor, taking into account the temperature coefficients of the reactivity; other applications of simulators in reactor design are indicated.     

多个核电项目堆内构件原材料PT漏检事件回顾与分析

堆内构件是核电厂反应堆冷却剂系统的主要设备。某制造厂在堆內构件制造过程中出现批量原材料PT漏检事件,造成大量人力和物力的浪费,影响到现场的工程进度。漏检事件反映出制造厂质量保证体系的缺陷,事件相关方应该加强质量管理和过程控制、做好经验反馈工作,提高我国的设备国产化水平,推动我国核电的平稳发展。     

核电站常规设备质量保证分级方法

根据系统、规范的质量保证分级方法对设备进行分级,可以合理地分配有限的资源,确保核电站关键设备的质量.本文结合对我国岭澳核电站一期工程项目中常规设备的分级方法的介绍,分析了分级的目的,对岭澳一期项目中常规设备分级中存在的问题,给出了既能实现合理分配资源,又具有较强可操作性的核电厂常规设备分级方法.     

核电厂及设备的寿期和剩余寿期预测分析方法的研究

截至目前,全世界已有450多座在运核电厂,其中相当一部分核电厂是70年代建造的,这些核电厂已达到或接近预定寿期,在这种情况下,不对其设备进行寿期预测、评估而继续运行,对安全是极为不利的。而对于还没有到预定寿期的核电厂,为了安全管理的需要,其设备的寿期及剩余寿期也应预测。同时,也应对设备运行及核电厂运行的经济性如何这些人们普遍关心的问题进行预测。该文的目的是给出核电厂及其设备寿期与剩余寿期的预测方法。其方法是:通过对核电厂运行的经济性分析,给出预测核电厂寿期的方法;通过损坏计算法和概率统计法及设备运行费用经济性分析的方法给出核电厂的设备寿期与剩余寿期的预测方法;结果是:正确地给出了核电厂及其设备寿期与剩余寿期的预测方法;结论是:该方法适用于核电厂及设备,也适用于其他行业如化工行业的设施及设备。     

核电厂新型H形防甩击件研究

本文阐述一种核电厂用创新型H形防甩击限制件(以下简称防甩击件)设计与研究。首先对新型H形防甩击件设计提出了性能要求并进行了结构设计,然后用动态分析软件模拟其力学性能(载荷位移)曲线,获得平稳的载荷位移曲线,从理论上证明该新型结构适用于防甩击件。最后进行实际模拟件试验,将试验结果与力学分析结果对比,从而验证理论分析的正确性,最终获得一种载荷位移曲线平稳且满足使用要求的新型防甩击件。     

Introduction of a quality management system at the Gemeinschaftskernkraftwerk Neckar GMBH (GKN)

In the course of commissioning unit II of the GKN nuclear power plant, a Quality Assurance Manual was introduced in 1988. The Quality Assurance Manual is essentially based on the quality assurance elements of KTA 1401; that is, the emphasis is on quality assurance procedures for safety relevant plant components. During the actual application of the Quality Assurance Manual, however, it soon became apparent that this one-dimensional approach to quality management is not sufficient for the efficient organization of the quality related operational processes and procedures. The management of GKN decided at the end of 1992 to carry out a revision of the Quality Assurance Manual, with the objective of using quality, within the meaning of DIN ISO 9001, as a comprehensive organizational element for all operational processes and procedures. BTB-Jansky GmbH, a consulting firm familiar with the operational processes and procedures was commissioned to revise the Quality Assurance Manual, to investigate the procedures and implement a quality management system. The introduction of the quality management system has made it possible for the quality relevant processes and procedures at GKN to be regulated comprehensively and in a systematically transparent and workable manner. The introduction of the quality management system took place within the framework of an efficiency raising programme. It becomes apparent from this that the introduction of a quality management system is able to provide economic benefits for the operator.     

The engineer's role in the assurance of quality

The reasons given most frequently for the lack of new nuclear plant construction are many and well documented. The authors of this paper feel that cost is probably the major reason and they point out that cost is greatly impacted by a failure to firmly establish, in an understandable manner, the role of the engineer in the assurance of quality. (In this paper the authors are talking about engineers and engineering responsibility; they are not talking about engineering organizations.) This misunderstanding is associated with the unnecessarily legalistic interpretation of requirements. This has caused unwarranted cost overruns and schedule delays. The cost and delays caused by the trivial concerns can be higher than $500 million and two years delay for each nuclear power plant. The system which caused the problem can, and must, be corrected. Engineers have allowed the system to replace our technical skills and practical approaches to solving problems, and the engineers must now take the initiative and change this system. The result will be better, more reliable and less costly products.     

基于LSTM的核电传感器多特征融合多步状态预测

针对核电工况参数预测的问题,利用核电站传感检测系统采集的大量时间序列,提出了基于长短时记忆网络（LSTM）的多特征融合多步状态预测模型。以某核电厂实时参数系统采集到的SG1蒸汽压力传感数据为研究对象,首先针对数据缺失、采样时标不一致问题进行数据预处理,然后完成基于LSTM的多特征融合多步状态预测模型的结构设计与建模,最后将本文提出的预测模型与循环神经网络（RNN）、门控循环单元（GRU）、本文模型-全连接层1以及单变量LSTM等多步预测模型进行比较。实验结果表明,本文提出的预测模型的拟合性能和预测性能整体最优,同时也验证了基于LSTM模型的深度学习方法在核电站运行安全保障领域的适用性。